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Effects of an internal thermocouple on the response of measured initial LOFT fuel centerline temperatures

Creators

  • 1. Siemens Power Corporation, Nuclear Division, Richland, WA (United States)

Description

The SPC fuel thermal-mechanical analysis code RODEX3 was applied to analyze the temperature response of fuel rods with standard solid pellets and fuel rods with annular pellets which contain an internal thermocouple, for the LOFT L2-5 and L2-6 large-break loss-of-coolant experiments. The analysis was performed to investigate the intrusive effect of an internal thermocouple on the response of LOFT fuel centerline temperatures by comparing measured data with the calculated temperatures of two fuel rods modeled as solid and annular pellets. The analysis results demonstrated that the intrusive effect of the internal thermocouple on the measured fuel centerline temperature is significant. Since the difference between the calculated solid and annular pellet centerline temperatures is large, the measured centerline temperature is actually an indication of the temperature of the inner surface temperature of the annular pellet. The solid pellet centerline temperature calculated to be is significantly greater than the temperature measured by an internal thermocouple. (author)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

Additional details

Publishing Information

Imprint Title
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2
Imprint Pagination
814 p.
Journal Page Range
p. 33D1-33D6
Report number
INIS-XA-N--081

Conference

Title
4. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
5-8 Apr 1994
Place
Taipei, Taiwan (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35097862
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANNULAR FUEL ELEMENTS; FUEL ELEMENTS; FUEL PELLETS; LOSS OF COOLANT; MATHEMATICAL MODELS; TEMPERATURE DISTRIBUTION; TEMPERATURE MEASUREMENT
Descriptors DEC
ACCIDENTS; FUEL ELEMENTS; PELLETS; REACTOR ACCIDENTS; REACTOR COMPONENTS

Optional Information

Notes
This record replaces 35095595; 7 refs, 8 figs